AFIP-2 Irradiation Summary Report

Technical Report · Sun May 01 00:00:00 EDT 2011

DOI:https://doi.org/10.2172/1023477· OSTI ID:1023477

Perez, Danielle M; Lillo, M A; Chang, G S; Roth, G A; Woolstenhulme, N E; Wachs, D M

The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-2 was designed to evaluate the performance of monolithic fuels at a prototypic scale of 2.25 inches x 21.5 inches x 0.050 inches (5.75 cm x 54.6 cm x 0.13cm). The AFIP-2 experiment was fabricated by friction bond (FB) and consists of two plates, one with a zirconium (Zr) diffusion barrier and one with a silicon (Si) enhanced fuel/clad interface1,2. The following report summarizes the life of the AFIP-2 experiment through end of irradiation, including a brief description of the safety analysis, as-run neutronic analysis results, hydraulic testing results, and thermal analysis results. The safety analyses performed for AFIP-2 are summarized in Table 5 of the following report.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: DOE - NE
• DOE Contract Number: DE-AC07-05ID14517
• OSTI ID: 1023477
• Report Number(s): INL/EXT-11-21599; TRN: US1104586
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
DIFFUSION BARRIERS
FRICTION
HYDRAULICS
IRRADIATION
PERFORMANCE
PLATES
SAFETY
SAFETY ANALYSIS
SILICON
TEST REACTORS
TESTING
THERMAL ANALYSIS
ZIRCONIUM
AFIP-2 Irradiation Summary Report